D. Power S. Mijin F. Militello R. Kingham
Tokamak edge (scrape-off layer) plasmas can exhibit non-local transport in the direction parallel to the magnetic field due to steep temperature gradients.This effect along with its consequences has been explored at equilibrium fora range of conditions, from sheath-limited to detached, using the 1D kinetic electron code SOL-KiT, where the electrons…
PreprintNick Walkden Fabio Riva James Harrison Fulvio Militello Tom Farley John Omotani
Fusion power plant designs based on magnetic confinement, such as the tokamak design, offer a promising route to sustainable fusion power but require robust exhaust solutions capable of tolerating intense heat and particle fluxes from the plasma to material surfaces. Turbulent plasma transport in the divertor volume – the region where the plasma-…
Preprint PublishedT. E. G. Nicholas J. Omotani F. Riva F. Militello B. Dudson
There exists a large body of previous work using reduced two-dimensional models of the SOL, which model fluctuations in the drift-plane but approximate parallel transport with effective loss terms. Full size three-dimensional simulations of SOL turbulence in experimental geometries are now possible, but are far more computationally expensive than …
Preprint PublishedH. J. Sun R. J. Goldston A. Huber X. Q. Xu J. Flanagan D. C. McDonald E. de la Luna M. Maslov J. R. Harrison F. Militello J. Fessey S. Cramp JET Contributors
A study of a dataset of JET H-mode plasma with the Be/W ITER-like wall (JET-ILW) shows that reaching the edge MHD ballooning limit leads to confinement degradation. However, unlike JET plasmas with a carbon wall (JET-C), the JET-ILW plasmas stay in a marginal dithering phase for a relatively long period, associated with a higher (20%) H-mode den…
Preprint PublishedJ. R. Harrison T. Farley G. M. Fishpool A. Kirk B. Lipschultz J. Lovell F. Militello D. Moulton P. Ryan R. Scannell A. J. Thornton K. Verhaegh L. Xiang
The benefits of an optimised Super-X divertor configuration in mitigating the steady-state power and particle fluxes to the surfaces of the MAST Upgrade divertor have been quantified by performing a detailed comparison with a conventional divertor for the first time. In otherwise identical plasmas with conventional and Super-X divertor configu…
PreprintA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
Preprint PublishedA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed. The assessment is performed on the basis of empirical and…
Preprint PublishedS. Mijin F. Militello S. Newton J.T. Omotani R.J. Kingham
We present the first parallel electron transport results obtained using the newly developed 1D transport code SOL-KiT. In order to properly predict divertor heat loads it is of key importance to develop a thorough understanding of discrepancies between different parallel transport modelling approaches. With the capability to self-consistently sw…
Preprint PublishedD. Russel J. Myra F. Militello D. Moulton
The 2D scrape-off-layer turbulence code (nSOLT) includes 1D Boltzmann neutral-plasma interactions, a model of divertor recycling (introduced here), and a fixed source of plasma concentrated at the core-side boundary. 1) Neutral injection in the far-SOL is accomplished by specifying the density of Franck-Condon distributed neutrals streaming in from…
Preprint PublishedD. Galassi C. Theiler T. Body F. Manke P. Micheletti J. Omotani M. Wiesenberger M. Baquero-Ruiz I. Furno M. Giacomin E. Laribi F. Militello P. Ricci A. Stegmeir P. Tamain H. Bufferand G. Ciraolo H. De Oliveira A. F. Fasoli V. Naulin S. L. Newton N. Offeddu D. Sales Oliveira E. Serre N. Vianello
Transport processes around the magnetic X-point of tokamaks, such as turbulence and mean-field drifts, are scarcely understood and difficult to investigate in experiments. In this paper, we explore the dynamics in a newly developed X-point scenario on the basic toroidal plasma device TORPEX and use it to validate plasma edge turbulence codes. In-si…
Preprint Published